skip navigation links 
 
 Search Options 
Index | Site Map | FAQ | Facility Info | Reading Rm | New | Help | Glossary | Contact Us blue spacer  
secondary page banner Return to NRC Home Page

EPRI/NRC-RES Fire PRA Methodology for Nuclear Power Facilities (NUREG/CR-6850)

On this page:

Download complete document

The following links on this page are to documents in Adobe Portable Document Format (PDF). See our Plugins, Viewers, and Other Tools page for more information. For successful viewing of PDF documents on our site please be sure to use the latest version of Adobe.


Publication Information

Date Published: September 2005

Prepared by
Science Applications International Corporation (SAIC)
4920 El Camino Real
Los Altos, CA 94022
Technical Program Manager
B. Najafi, SAIC

Sandia National Laboratories (SNL)
1515 Eubank SE
Albuquerque, NM 87185

Technical Program Manager
S. P. Nowlen, SNL

Prepared for
Electric Power Research Institute (EPRI)
3412 Hillview Avenue
Palo Alto, CA 94303

EPRI Project Manager
R. P. Kassawara

Division of Risk Analysis and Applications
Office of Nuclear Regulatory Research (RES)
U.S. Nuclear Regulatory Commission
Two White Flint North, 11545 Rockville Pike
Rockville, MD 20852-2738

U.S. NRC-RES Project Manager
J. S. Hyslop

Availability Notice


Abstract

This report documents state-of-the-art methods, tools, and data for the conduct of a fire Probabilistic Risk Assessment (PRA) for a commercial nuclear power plant (NPP) application. This report is intended to serve the needs of a fire risk analysis team by providing a structured framework for conduct of the overall analysis, as well as specific recommended practices to address each key aspect of the analysis. The methods have been developed under the Fire Risk Requantification Study. This study was conducted as a joint activity between the Electric Power Research Institute (EPRI) and the U.S. Nuclear Regulatory Commission (NRC) Office of Nuclear Regulatory Research (RES) under the terms of an NRC/EPRI Memorandum of Understanding and an accompanying Fire Risk Addendum. Participants from the U.S. Nuclear Power Industry supported demonstration analyses and provided peer review of this methodology. Methodological issues raised in past fire risk analyses, including the Individual Plant Examination of External Events (IPEEE) fire analyses, have been addressed to the extent allowed by the current state-of-the-art and the overall project scope. While the primary objective of the project was to consolidate existing state-of-the-art methods, in many areas, the newly documented methods represent a significant advancement over previously documented methods.



Privacy Policy | Site Disclaimer
Friday, February 23, 2007